ENTRY 22990 20130920 22352299000000001
SUBENT 22990001 20130920 22352299000100001
BIB 19 142 2299000100002
TITLE (n,xn gamma) reaction cross section measurements for 2299000100003
(n,xn) reaction studies. 2299000100004
AUTHOR (M.Kerveno, J.C.Thiry, A.Bacquias, C.Borcea,P.Dessagne,2299000100005
J.C.Drohe,N.Nankov,M.Nyman,A.Negret,A.Plompen,C.Rouki, 2299000100006
G.Rudolf,M.Stanoiu, E.Jericha, H.Karam, A.J.Koning, 2299000100007
A.Pavlik) 2299000100008
INSTITUTE (2ZZZGEL) J.C.Drohe,A.Plompen,C.Rouki,N.Nankov,M.Nyman 2299000100009
(2FR STR) J.C.Thiry, P.Dessagne,H.Karam, M.Kerveno, 2299000100010
G.Rudolf, M.Stanoiu, A.Bacquias. 2299000100011
(3RUMBUC) C.Borcea, A.Negret. 2299000100012
(2AUSATI) E.Jericha. 2299000100013
(2NEDNRG) A.J.Koning. 2299000100014
(2AUSVIE) A.Pavlik. 2299000100015
(2GERPTB) Facility to measure efficiency of fission 2299000100016
chamber. 2299000100017
REFERENCE (J,EPJ/CS,42,01005,2013) First author M.Kerveno. 2299000100018
#doi:10.1051/epjconf/20134201005 2299000100019
U-235, U-238, Th-232, W-184 prelim.c-s on figures only.2299000100020
(T,THIRY,20100930) Ph.D.thesis of J.-C.Thiry. 2299000100021
Tables of preliminary results for U-235,Th-232. 2299000100022
(J,KPS,59,1880,2011) ND2010 Conf.Proc. paper #1483; 2299000100023
in ND2010 Abstract book, page 28. 2299000100024
Figures only for U-235, Th-232 . 2299000100025
First author J.C.Thiry. 2299000100026
(C,2010KRAKOW,93,2010) Figures only for U-235,Th-232. 2299000100027
First author M.Kerveno. 2299000100028
(C,2010KRAKOW,121,2010) Details of fission chamber 2299000100029
used for neutron flux measurement. 2299000100030
NEMEA-6 Workshop Proceedings is available online 2299000100031
at web-site www.oecd-nea.org/science/wpec/nemea6 . 2299000100032
FACILITY (LINAC,2ZZZGEL) GELINA facility FP16/30m. 2299000100033
INC-SOURCE (BRST,PHOTO) Electron beam strikes a depleted uranium 2299000100034
target producing bremsstrahlung and neutrons by 2299000100035
(gamma,xn) and (gamma,F) reactions. 2299000100036
INC-SPECT Pulsed white neutron source GELINA. 2299000100037
Differential neutron flux is on Fig.2 of 2299000100038
J,KPS,58,(1483),2011 , Fig.5.3 of T,THIRY,2010, 2299000100039
Fig.2 of C,2010KRAKOW,93 , Fig.2 of C,2010KRAKOW,121. 2299000100040
Flux was measured using U-235 fission chamber with 2299000100041
a vacuum evaporated U-235-F(4) deposit of U-235 2299000100042
enrichment > 99.5%, and 324. microg/cm**2 thickness 2299000100043
of U-235. 2299000100044
SAMPLE U-235: 2299000100045
purity 93.18%, atomic mass 235.043923 g/mol,total mass 2299000100046
37.43+-0.01 g, surface 113.173 cm**2, thickness 2299000100047
0.211+-0.006 mm, density 15.67 g/cm**3, areal density 2299000100048
0.330+-0.009 g/cm**2 . 2299000100049
Th-232: 2299000100050
purity 99.5%, atomic mass 232.038050 g/mol,total mass 2299000100051
11.9939+-0.0001 g, surface 36.463 cm**2, thickness 2299000100052
0.302+-0.004 mm, density 10.894 g/cm**3, areal density 2299000100053
0.329-0.004 g/cm**2 2299000100054
METHOD (TOF) Flight path 30 meters. Time resolution 10 ns. 2299000100055
Neutron energy resolution 0.86 MeV at 20 MeV, 0.3 keV 2299000100056
at 100 keV neutron energy. Exact sample distance 2299000100057
28.817+-0.001 m. 2299000100058
DETECTOR (HPGE) Four semi-planar n-type high purity germanium 2299000100059
HPGe counters (of Canberra), made 2299000100060
of planar crystals with depths ranging from 2 to 3 cm 2299000100061
and surfaces between 10 and 28 cm2; were optimized for 2299000100062
high resolution detection at low energies (resolution 2299000100063
of 0.7 keV at 122 keV); were placed at angles of 110 2299000100064
and 149 degrees, placed at distances 167.6, 218.7, 2299000100065
141.0, 134.6 mm from sample. 2299000100066
Special lead shielding - to eliminate background 2299000100067
radiation. 2299000100068
Eu-152 sources of 2 and 50 mm diameter and Ba-133 point2299000100069
source were used for calibration. Geant4 code 2299000100070
simulations were compared with measured gamma-emission.2299000100071
(FISCH) The flux was measured by double layer U-235 2299000100072
fission chamber. The deposits, enriched in U-235 2299000100073
(>99.5 %), 2299000100074
1) 323.757+-1.740 microg/cm**2 , the vacuum evaporated 2299000100075
U-235F(4) layer, 6.7 g/cm**3, 7.00 cm diameter, 2299000100076
38.48 cm**2 surface, 639.52 nm thickness,12.46 microg 2299000100077
U mass, 8.2978E17 at/cm**2, position 27.2601 m; 2299000100078
2) 387+-3 microg/cm**2, the spray painted U-235(3)O(8) 2299000100079
layer, position 27.4151m, 8.38 g/cm**3, 10.16 cm 2299000100080
diameter, 81.07 cm**2 surface, 545.7 nm thickness, 2299000100081
31.38 mg U mass, 9.919E17 at/cm**2. 2299000100082
Located at 27.260 m flight distance. 2299000100083
Operated at gas pressure 1 atm. 2299000100084
Additional precise calibration measurement was made 2299000100085
at PTB, Braunschweig, at neutron energy 8.39+-0.04 MeV 2299000100086
using fission c-s 1.793+-0.014 b from interpolation of 2299000100087
ENDF/B-VII.0 data, leads to exp. efficiency of 2299000100088
(94.4+-2.1) %. 2299000100089
Only UF4 deposit was used for the flux determination. 2299000100090
DECAY-DATA (63-EU-152,13.51YR) 13.51+-0.03 yr. 2299000100091
Eu-152 data used in analysis of HPGE efficiency 2299000100092
uncertainty determination: 2299000100093
Gamma energy,keV Branching ratio Error on emitted 2299000100094
particles 2299000100095
45.4+46.6 14.95+-0.47 3.22 % 2299000100096
121.78 28.48+-0.13 0.85 % 2299000100097
244.70 7.53+-0.04 0.90 % 2299000100098
344.28 26.57+-0.11 0.83 % 2299000100099
443.97 3.13+-0.01 0.89 % 2299000100100
778.90 12.98+-0.06 0.88 % 2299000100101
964.06 14.64+-0.06 0.85 % 2299000100102
1085.84 11.87+-0.05 0.87 % 2299000100103
PART-DET (G) Identified gamma-energies of U-235 energy spectra 2299000100104
are given in table B.1 of T,THIRY,2010; 2299000100105
of Th-232 - in Table B.2 . 2299000100106
MONITOR (92-U-235(N,F),,SIG) For neutron flux. 2299000100107
MONIT-REF (,,3,ENDF/B-VII.0,,2006) 2299000100108
ERR-ANALYS (ERR-1,2.3,2.9) Uncertainty of neutron spectrum - 2299000100109
2.9% at high energy, 2.3 in 1-2 MeV neutron energy 2299000100110
region; calculated using 2299000100111
0.3% uncertainty on the areal density of nuclei in 2299000100112
deposit, 2299000100113
2.1 % on fission chamber efficiency, 2299000100114
up to 1 % on fission cross-section from ENDF/B-VII.0, 2299000100115
1.5% on air attenuation coefficient, 2299000100116
< 1% on counting statistics. 2299000100117
(ERR-2) Uncertainty of fission chamber efficiency . 2299000100118
CORRECTION For dead time of factor from 1.03 to 1.6. 2299000100119
For backgrounds. 2299000100120
For the loss of fission fragments inside the deposit 2299000100121
of ionization chamber. 2299000100122
For back-scattering of the second fission product 2299000100123
into active volume of the chamber. 2299000100124
For the lost due to the application of energy 2299000100125
threshold. 2299000100126
Measured neutron flux was corrected to take into 2299000100127
account the effective neutron yield hitting the sample 2299000100128
(flux was measured 1.56m before the sample) - 1.8 %. 2299000100129
ADD-RES (ANGD) Angular gamma-production cross-sections (b/sr) 2299000100130
fro gamma energies of Subents 002-011 are given on 2299000100131
Figures C.1-C.10 of T,THIRY,2010. 2299000100132
STATUS (COREL,23138001) Data for U-235. 2299000100133
(COREL,23104001) Data for W. 2299000100134
(COREL,22795001) U-238 data. 2299000100135
HISTORY (20110727C) M.M. 2299000100136
ENTRY was sent 01-08-2011 for approve to 2299000100137
Jean Claude Thiry - jean-claude.thiry@ires.in2p3.fr 2299000100138
(20121018A) NEA DB - DATA in subentries were 2299000100139
deleted at the authors' request. Final data will be 2299000100140
provided after final publication of the results. 2299000100141
(20130920T) M.M. Data for Th, Subents 006-019 from 2299000100142
Entry 23138 were moved in this Entry 22990, Subents 2299000100143
002-015, respectively . 2299000100144
ENDBIB 142 0 2299000100145
COMMON 1 3 2299000100146
ERR-2 2299000100147
PER-CENT 2299000100148
2.1 2299000100149
ENDCOMMON 3 0 2299000100150
ENDSUBENT 149 0 2299000199999
SUBENT 22990002 20130920 22352299000200001
BIB 6 10 2299000200002
REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299000200003
Gamma-ray transition cross section for the 112.75 keV 2299000200004
transition 4+ -> 2+ of Th-232. 2299000200005
CORRECTION For dead time- using 238.6 keV gamma-ray by decay of 2299000200006
Bi-212. 2299000200007
COMMENT The data has been acquired within 375 hours. 2299000200008
EN-SEC (E,G) Energy of gamma transition. 2299000200009
ADD-RES (COMP) Compared with TALYS code calculation. 2299000200010
STATUS (PRELM) Table C.5 of T,THIRY,2010. 2299000200011
Data are on Fig.6 right of C,2010KRAKOW . 2299000200012
ENDBIB 10 0 2299000200013
COMMON 3 3 2299000200014
E LVL-INI LVL-FIN 2299000200015
KEV KEV KEV 2299000200016
112.75 162.12 49.37 2299000200017
ENDCOMMON 3 0 2299000200018
NODATA 0 0 2299000200019
ENDSUBENT 18 0 2299000299999
SUBENT 22990003 20130920 22352299000300001
BIB 6 10 2299000300002
REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299000300003
Gamma-ray transition cross section for the 171.2 keV 2299000300004
transition 6+ -> 4+ of Th-232. 2299000300005
CORRECTION For dead time- using 238.6 keV gamma-ray by decay of 2299000300006
Bi-212. 2299000300007
COMMENT The data has been acquired within 375 hours. 2299000300008
EN-SEC (E,G) Energy of gamma transition. 2299000300009
ADD-RES (COMP) Compared with TALYS code calculation. 2299000300010
STATUS (PRELM) Table C.6 of T,THIRY,2010. 2299000300011
Data are on Fig.6 right of C,2010KRAKOW . 2299000300012
ENDBIB 10 0 2299000300013
COMMON 3 3 2299000300014
E LVL-INI LVL-FIN 2299000300015
KEV KEV KEV 2299000300016
171.2 333.3 162.1 2299000300017
ENDCOMMON 3 0 2299000300018
NODATA 0 0 2299000300019
ENDSUBENT 18 0 2299000399999
SUBENT 22990004 20130920 22352299000400001
BIB 6 10 2299000400002
REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299000400003
Gamma-ray transition cross section for the 223.6 keV 2299000400004
transition 8+ -> 6+ of Th-232. 2299000400005
CORRECTION For dead time- using 238.6 keV gamma-ray by decay of 2299000400006
Bi-212. 2299000400007
COMMENT The data has been acquired within 375 hours. 2299000400008
EN-SEC (E,G) Energy of gamma transition. 2299000400009
ADD-RES (COMP) Compared with TALYS code calculation. 2299000400010
STATUS (PRELM) Table C.7 of T,THIRY,2010. 2299000400011
Data are on Fig.6 right of C,2010KRAKOW . 2299000400012
ENDBIB 10 0 2299000400013
COMMON 3 3 2299000400014
E LVL-INI LVL-FIN 2299000400015
KEV KEV KEV 2299000400016
223.6 556.9 333.3 2299000400017
ENDCOMMON 3 0 2299000400018
NODATA 0 0 2299000400019
ENDSUBENT 18 0 2299000499999
SUBENT 22990005 20130920 22352299000500001
BIB 6 10 2299000500002
REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299000500003
Gamma-ray transition cross section for the 49.37 keV 2299000500004
transition 2+ -> 0+ of Th-232. 2299000500005
CORRECTION For dead time- using 238.6 keV gamma-ray by decay of 2299000500006
Bi-212. 2299000500007
COMMENT The data has been acquired within 375 hours. 2299000500008
EN-SEC (E,G) Energy of gamma transition. 2299000500009
ADD-RES (COMP) Compared with TALYS code calculation. 2299000500010
STATUS (PRELM) Table C.8 of T,THIRY,2010. 2299000500011
Data are on Fig.6 left of C,2010KRAKOW . 2299000500012
ENDBIB 10 0 2299000500013
COMMON 3 3 2299000500014
E LVL-INI LVL-FIN 2299000500015
KEV KEV KEV 2299000500016
49.37 49.37 0. 2299000500017
ENDCOMMON 3 0 2299000500018
NODATA 0 0 2299000500019
ENDSUBENT 18 0 2299000599999
SUBENT 22990006 20130920 22352299000600001
BIB 6 10 2299000600002
REACTION (90-TH-232(N,2N)90-TH-231,PAR,SIG,G) 2299000600003
Gamma-ray transition cross section for the 185.7 keV 2299000600004
transition 5/2- -> 5/2+ of Th-231. 2299000600005
CORRECTION For dead time- using 238.6 keV gamma-ray by decay of 2299000600006
Bi-212. 2299000600007
COMMENT The data has been acquired within 375 hours. 2299000600008
EN-SEC (E,G) Energy of gamma transition. 2299000600009
ADD-RES (COMP) Compared with TALYS code calculation. 2299000600010
STATUS (PRELM) Table C.9 of T,THIRY,2010. 2299000600011
Data are on Fig.8 left of C,2010KRAKOW . 2299000600012
ENDBIB 10 0 2299000600013
COMMON 3 3 2299000600014
E LVL-INI LVL-FIN 2299000600015
KEV KEV KEV 2299000600016
185.7 185.7 0. 2299000600017
ENDCOMMON 3 0 2299000600018
NODATA 0 0 2299000600019
ENDSUBENT 18 0 2299000699999
SUBENT 22990007 20130920 22352299000700001
BIB 6 10 2299000700002
REACTION (90-TH-232(N,3N)90-TH-230,PAR,SIG,G) 2299000700003
Gamma-ray transition cross section for the 182.5 keV 2299000700004
transition 6+ -> 4+ of Th-230. 2299000700005
CORRECTION For dead time- using 238.6 keV gamma-ray by decay of 2299000700006
Bi-212. 2299000700007
COMMENT The data has been acquired within 375 hours. 2299000700008
EN-SEC (E,G) Energy of gamma transition. 2299000700009
ADD-RES (COMP) Compared with TALYS code calculation. 2299000700010
STATUS (PRELM) Table C.10 of T,THIRY,2010. 2299000700011
Data are on Fig.8 right of C,2011KRAKOW . 2299000700012
ENDBIB 10 0 2299000700013
COMMON 3 3 2299000700014
E LVL-INI LVL-FIN 2299000700015
KEV KEV KEV 2299000700016
182.5 356.5 174.10 2299000700017
ENDCOMMON 3 0 2299000700018
NODATA 0 0 2299000700019
ENDSUBENT 18 0 2299000799999
SUBENT 22990008 20130920 22352299000800001
BIB 4 7 2299000800002
REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299000800003
Gamma-ray transition cross section for the 550.4 keV 2299000800004
transition L13 -> L3 of Th-232. 2299000800005
EN-SEC (E,G) Energy of gamma transition. 2299000800006
ADD-RES (COMP) Compared with TALYS code calculation. 2299000800007
STATUS (PRELM) Preliminary data. 2299000800008
Data are on Fig.7 left top of C,2011KRAKOW . 2299000800009
ENDBIB 7 0 2299000800010
COMMON 1 3 2299000800011
E 2299000800012
KEV 2299000800013
550.4 2299000800014
ENDCOMMON 3 0 2299000800015
NODATA 0 0 2299000800016
ENDSUBENT 15 0 2299000899999
SUBENT 22990009 20130920 22352299000900001
BIB 4 7 2299000900002
REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299000900003
Gamma-ray transition cross section for the 611.8 keV 2299000900004
transition L8 -> L2 of Th-232. 2299000900005
EN-SEC (E,G) Energy of gamma transition. 2299000900006
ADD-RES (COMP) Compared with TALYS code calculation. 2299000900007
STATUS (PRELM) Preliminary data. 2299000900008
Data are on Fig.7 middle top of C,2011KRAKOW . 2299000900009
ENDBIB 7 0 2299000900010
COMMON 1 3 2299000900011
E 2299000900012
KEV 2299000900013
611.8 2299000900014
ENDCOMMON 3 0 2299000900015
NODATA 0 0 2299000900016
ENDSUBENT 15 0 2299000999999
SUBENT 22990010 20130920 22352299001000001
BIB 4 7 2299001000002
REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299001000003
Gamma-ray transition cross section for the 665.0 keV 2299001000004
transition L5 -> L1 of Th-232. 2299001000005
EN-SEC (E,G) Energy of gamma transition. 2299001000006
ADD-RES (COMP) Compared with TALYS code calculation. 2299001000007
STATUS (PRELM) Preliminary data. 2299001000008
Data are on Fig.7 right top of C,2011KRAKOW . 2299001000009
ENDBIB 7 0 2299001000010
COMMON 1 3 2299001000011
E 2299001000012
KEV 2299001000013
665.0 2299001000014
ENDCOMMON 3 0 2299001000015
NODATA 0 0 2299001000016
ENDSUBENT 15 0 2299001099999
SUBENT 22990011 20130920 22352299001100001
BIB 4 7 2299001100002
REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299001100003
Gamma-ray transition cross section for the 714.2 keV 2299001100004
transition L5 -> L0 of Th-232. 2299001100005
EN-SEC (E,G) Energy of gamma transition. 2299001100006
ADD-RES (COMP) Compared with TALYS code calculation. 2299001100007
STATUS (PRELM) Preliminary data. 2299001100008
Data are on Fig.7 left bottom of C,2011KRAKOW . 2299001100009
ENDBIB 7 0 2299001100010
COMMON 2 3 2299001100011
E LVL-FIN 2299001100012
KEV KEV 2299001100013
714.2 0. 2299001100014
ENDCOMMON 3 0 2299001100015
NODATA 0 0 2299001100016
ENDSUBENT 15 0 2299001199999
SUBENT 22990012 20130920 22352299001200001
BIB 4 7 2299001200002
REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299001200003
Gamma-ray transition cross section for the 735.9 keV 2299001200004
transition L9 -> L1 of Th-232. 2299001200005
EN-SEC (E,G) Energy of gamma transition. 2299001200006
ADD-RES (COMP) Compared with TALYS code calculation. 2299001200007
STATUS (PRELM) Preliminary data. 2299001200008
Data are on Fig.7 middle bottom of C,2011KRAKOW . 2299001200009
ENDBIB 7 0 2299001200010
COMMON 1 3 2299001200011
E 2299001200012
KEV 2299001200013
735.9 2299001200014
ENDCOMMON 3 0 2299001200015
NODATA 0 0 2299001200016
ENDSUBENT 15 0 2299001299999
SUBENT 22990013 20130920 22352299001300001
BIB 4 7 2299001300002
REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299001300003
Gamma-ray transition cross section for the 780.2 keV 2299001300004
transition L11 -> L1 of Th-232. 2299001300005
EN-SEC (E,G) Energy of gamma transition. 2299001300006
ADD-RES (COMP) Compared with TALYS code calculation. 2299001300007
STATUS (PRELM) Preliminary data. 2299001300008
Data are on Fig.7 middle bottom of C,2011KRAKOW . 2299001300009
ENDBIB 7 0 2299001300010
COMMON 1 3 2299001300011
E 2299001300012
KEV 2299001300013
780.2 2299001300014
ENDCOMMON 3 0 2299001300015
NODATA 0 0 2299001300016
ENDSUBENT 15 0 2299001399999
SUBENT 22990014 20130920 22352299001400001
BIB 4 7 2299001400002
REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299001400003
Gamma-ray transition cross section for the 681.1 keV 2299001400004
transition L6 -> L1 of Th-232. 2299001400005
EN-SEC (E,G) Energy of gamma transition. 2299001400006
ADD-RES (COMP) Compared with TALYS code calculation. 2299001400007
STATUS (PRELM) Preliminary data. 2299001400008
Data are on Fig.7 right bottom of C,2011KRAKOW . 2299001400009
ENDBIB 7 0 2299001400010
COMMON 1 3 2299001400011
E 2299001400012
KEV 2299001400013
681.1 2299001400014
ENDCOMMON 3 0 2299001400015
NODATA 0 0 2299001400016
ENDSUBENT 15 0 2299001499999
SUBENT 22990015 20130920 22352299001500001
BIB 4 7 2299001500002
REACTION (90-TH-232(N,INL)90-TH-232,PAR,SIG,G) 2299001500003
Gamma-ray transition cross section for the 774.1 keV 2299001500004
transition L7 -> L0 of Th-232. 2299001500005
EN-SEC (E,G) Energy of gamma transition. 2299001500006
ADD-RES (COMP) Compared with TALYS code calculation. 2299001500007
STATUS (PRELM) Preliminary data. 2299001500008
Data are on Fig.7 right bottom of C,2011KRAKOW . 2299001500009
ENDBIB 7 0 2299001500010
COMMON 2 3 2299001500011
E LVL-FIN 2299001500012
KEV NO-DIM 2299001500013
774.1 0. 2299001500014
ENDCOMMON 3 0 2299001500015
NODATA 0 0 2299001500016
ENDSUBENT 15 0 2299001599999
ENDENTRY 15 0 2299099999999